US11424046B2 - Electronic enclosure with neutron shield for nuclear in-core applications - Google Patents
Electronic enclosure with neutron shield for nuclear in-core applications Download PDFInfo
- Publication number
- US11424046B2 US11424046B2 US16/210,407 US201816210407A US11424046B2 US 11424046 B2 US11424046 B2 US 11424046B2 US 201816210407 A US201816210407 A US 201816210407A US 11424046 B2 US11424046 B2 US 11424046B2
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- neutron
- enclosure
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- electronic components
- reflecting
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- 239000000463 material Substances 0.000 claims abstract description 30
- 239000007787 solid Substances 0.000 claims abstract description 30
- 239000011358 absorbing material Substances 0.000 claims abstract description 26
- 239000000843 powder Substances 0.000 claims description 28
- 229910052688 Gadolinium Inorganic materials 0.000 claims description 15
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 claims description 14
- 239000000919 ceramic Substances 0.000 claims description 11
- 229910052790 beryllium Inorganic materials 0.000 claims description 8
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 claims description 6
- 150000001875 compounds Chemical class 0.000 claims description 6
- 239000012780 transparent material Substances 0.000 claims description 6
- 229910052793 cadmium Inorganic materials 0.000 claims description 4
- 229910052735 hafnium Inorganic materials 0.000 claims description 4
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical class [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims description 3
- 229910052796 boron Inorganic materials 0.000 claims description 3
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical class [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 claims description 3
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical class [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 claims description 3
- 239000000203 mixture Substances 0.000 claims description 3
- 150000002736 metal compounds Chemical class 0.000 claims 1
- 239000003758 nuclear fuel Substances 0.000 description 10
- 239000000446 fuel Substances 0.000 description 8
- CMIHHWBVHJVIGI-UHFFFAOYSA-N gadolinium(iii) oxide Chemical compound [O-2].[O-2].[O-2].[Gd+3].[Gd+3] CMIHHWBVHJVIGI-UHFFFAOYSA-N 0.000 description 6
- 229910052751 metal Inorganic materials 0.000 description 6
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- -1 beryllium nitrides Chemical class 0.000 description 5
- 230000000694 effects Effects 0.000 description 5
- 229910001938 gadolinium oxide Inorganic materials 0.000 description 5
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 4
- 229910010293 ceramic material Inorganic materials 0.000 description 4
- 230000005855 radiation Effects 0.000 description 4
- FRWYFWZENXDZMU-UHFFFAOYSA-N 2-iodoquinoline Chemical compound C1=CC=CC2=NC(I)=CC=C21 FRWYFWZENXDZMU-UHFFFAOYSA-N 0.000 description 3
- 239000003990 capacitor Substances 0.000 description 3
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
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- 229940075613 gadolinium oxide Drugs 0.000 description 2
- 239000004615 ingredient Substances 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
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- 238000012360 testing method Methods 0.000 description 2
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 229910052810 boron oxide Inorganic materials 0.000 description 1
- CXKCTMHTOKXKQT-UHFFFAOYSA-N cadmium oxide Inorganic materials [Cd]=O CXKCTMHTOKXKQT-UHFFFAOYSA-N 0.000 description 1
- CFEAAQFZALKQPA-UHFFFAOYSA-N cadmium(2+);oxygen(2-) Chemical class [O-2].[Cd+2] CFEAAQFZALKQPA-UHFFFAOYSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
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- WIHZLLGSGQNAGK-UHFFFAOYSA-N hafnium(4+);oxygen(2-) Chemical class [O-2].[O-2].[Hf+4] WIHZLLGSGQNAGK-UHFFFAOYSA-N 0.000 description 1
- 239000008240 homogeneous mixture Substances 0.000 description 1
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- 238000009377 nuclear transmutation Methods 0.000 description 1
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Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F3/00—Shielding characterised by its physical form, e.g. granules, or shape of the material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/10—End closures ; Means for tight mounting therefor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/102—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain the sensitive element being part of a fuel element or a fuel assembly
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
- G21F1/08—Metals; Alloys; Cermets, i.e. sintered mixtures of ceramics and metals
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/12—Laminated shielding materials
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/12—Laminated shielding materials
- G21F1/125—Laminated shielding materials comprising metals
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
- G21C3/18—Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
- G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
Definitions
- the invention relates to enclosures for use in nuclear fuel rods to shield in-core electronic components.
- Sensors are placed in and around nuclear reactors to monitor conditions within the reactor. Tests have shown that some electronic sensors, such as non-organic capacitors, inductors, and surge arrestor gas discharge tubes, will operate at conditions equivalent to the elevated temperatures and radiation environments found in pressurized water reactors (PWR), but that the long term stability and drift of their operating parameters degrade over time. For example, a capacitor's capacitance, an inductor's inductance, or a gas discharge tube's break down voltage will degrade under the conditions present in nuclear reactors.
- PWR pressurized water reactors
- the sensors placed in reactors are exposed to ionizing radiation from both neutrons and gamma radiation. Over time, the radiation will interact with the materials in the electronic components of the sensors to impact performance and in many cases cause damage to the sensors.
- the effects of gamma radiation have been found to be predominantly transient in nature or only present when the irradiation field is present and cumulative damage to the microstructure is minimal.
- the effect of neutron exposure produces damage cascades of permanent voids and interstitials within the material and in some cases cause transmutation reactions to occur.
- the effects of the neutrons on the material used in sensors are both permanent and cumulative, whereas the effects of gamma irradiation are predominantly short lived and non-cumulative.
- the damaging effects of neutron exposure described above can be significantly delayed or reduced, if not avoided entirely, by enclosing the non-organic components of sensors necessary to the operation and monitoring of a nuclear reactor within an electronic enclosure equipped with a neutron shield as described herein. Having such a neutron shield will stabilize the performance of the sensors and slow down the long term degradation of the components due to neutron interactions.
- the enclosure would reside within the inner diameter of a typical nuclear fuel rod.
- the enclosure would be able to withstand neutron flux levels typically seen in the core of a commercial PWR reactor.
- the enclosure should withstand temperatures greater than 350° C.
- an electronics enclosure having neutron shielding properties will enable real time data recovery during testing of new fuel and cladding designs and in actual operation of nuclear reactors.
- the electronics enclosure with neutron shielding properties described herein may isolate the electronic components from electrically conductive fuel rods.
- the electronics enclosure with neutron shielding properties described herein may provide the opportunity to shield non-organic electronics from neutrons and extend the time required to reach a target fluence.
- An enclosure for non-organic electronic components includes a supporting structure that defines an inner cavity for housing non-organic electronic components, and a neutron barrier formed from neutron reflecting materials and neutron absorbing materials.
- the neutron barrier shields the electronic components when the components are housed in the cavity from neutrons, such as those generated in a nuclear reactor core.
- the neutron barrier may comprise a solid neutron reflecting layer surrounding the neutron absorbing material, and in certain aspects, the solid neutron reflecting layer may be the supporting structure.
- the neutron absorbing material may be in the form of a solid inner layer adjacent to and surrounding the cavity, being positioned in between the solid neutron reflecting layer and the cavity. Alternatively, the neutron absorbing material may be in the form of a powder filling the cavity and, in use, surrounding the electronic components.
- the supporting structure may be an outer structural layer made of a neutron transparent material, such as a solid ceramic material that neither reflects nor absorbs neutrons.
- the supporting structure may surround a solid neutron reflecting layer, which in turn may surround either a solid neutron absorbing material that surrounds the cavity, or a powdered neutron absorbing material within the cavity.
- the supporting structure may surround the cavity and the neutron barrier may be comprised of neutron reflecting material and neutron absorbing material in the form of powders contained within the cavity.
- the neutron reflecting and neutron absorbing powders may form a mixture filling the cavity and, in use, surrounding the electronic components.
- the neutron reflecting powder and the neutron absorbing powder may be disposed in layers, wherein the neutron absorbing powder layer is disposed adjacent to and surrounding the cavity and the neutron reflecting powder layer is disposed between the solid ceramic supporting structure and the neutron absorbing powder layer.
- the neutron reflecting powder and the neutron absorbing powder may be disposed in multiple alternating layers within the cavity.
- the neutron reflecting powder may be disposed in a layer in the cavity adjacent to the solid ceramic layer and the neutron absorbing powder may fill the cavity and in use, surround the electronic components.
- An embodiment of the enclosure described herein may be for use in a nuclear fuel rod wherein the fuel rod has a section for containing nuclear fuel.
- the enclosure includes an outer structural layer defining an inner cavity for receiving, in use, non-organic electronic components, a neutron barrier disposed between the structural layer and the cavity, the neutron barrier comprising at least one neutron reflecting layer and at least one neutron absorbing layer, and a forward neutron absorbing layer positioned between the section for containing nuclear fuel and the cavity.
- FIG. 1 A shows an embodiment of a form of the electronic enclosure described herein.
- FIG. 1 B shows a section view along the line A-A of the embodiment of the electronic enclosure shown in FIG. 1 A.
- FIG. 1 C shows a section view along the line B-B of the embodiment of the electronic enclosure shown in FIG. 1 A.
- FIG. 2 is a schematic illustration of an embodiment of the electronics enclosure showing a neutron barrier functioning as the support structure with a solid neutron reflective layer and a solid neutron absorbing layer surrounding the electronics cavity.
- FIG. 3 is a schematic illustration of a distinct solid support structure surrounding the solid neutron reflective and absorbing barrier layers of FIG. 2 .
- FIG. 4 is a schematic illustration of an embodiment of the electronics enclosure showing a solid support structure formed from a neutron transparent material surrounding a neutron barrier having a solid reflecting barrier surrounding an electronics cavity filled with a neutron absorbing material in powdered form to fill those spaces in the cavity that are not occupied by electronic components (not shown).
- FIG. 5 is a schematic cross-sectional illustration of a nuclear fuel rod having an embodiment of an electronics enclosure positioned within the fuel rod, above fuel pellets wherein the electronics enclosure includes a first neutron barrier in the form of powdered reflective and absorbing barrier materials filling those spaces in the cavity that are not occupied by electronic components (not shown) and a second neutron barrier positioned between the electronics cavity and the stack of fuel pellets.
- a first neutron barrier in the form of powdered reflective and absorbing barrier materials filling those spaces in the cavity that are not occupied by electronic components (not shown) and a second neutron barrier positioned between the electronics cavity and the stack of fuel pellets.
- any numerical range recited herein is intended to include all sub-ranges subsumed therein.
- a range of “1 to 10” is intended to include any and all sub-ranges between (and including) the recited minimum value of 1 and the recited maximum value of 10, that is, having a minimum value equal to or greater than 1 and a maximum value of equal to or less than 10.
- Sensitive electronic components needed in nuclear fuel assemblies may be protected from exposure to neutrons by enclosing the components in an electronics enclosure 10 equipped with a neutron barrier 20 according to the various embodiments described herein.
- an embodiment of the electronics enclosure 10 includes an enclosure body 14 and a lid 12 .
- An internal cavity 18 houses non-organic sensors and other electronic components (not shown) critical for various instrumentation and measurement applications.
- the sensors may include, for example, transmitters, capacitors, and detectors for measuring environmental conditions, such as in-core radioactivity sensors, thermocouple sensors, temperature sensors, pressure sensors and the like.
- the cavity 18 may be made into any shape best suited to house the particular non-organic components to be placed in the enclosure 10 .
- the cavity 18 may include one or more separate compartments 32 of a different size to accommodate different components.
- the compartments 32 may be separated from cavity 18 by a wall 34 or may be continuous.
- Cavity 18 also includes passages 28 and 36 through which wires for the electronic components may pass out of and through the enclosure 10 , respectively.
- Lid 12 may include threaded holes 30 leading into cavity 18 for placement of screws (not shown) to hold the electronics in place within the cavity 18 to prevent movement or shifting of the electronic components.
- lid 12 is attached to body 14 with screws or other fasteners 16 .
- cavity 18 may be one single cavity of uniform or non-uniform dimensions.
- enclosure 10 is made of a ceramic based material.
- the enclosure 10 is designed to fit within the inner diameter of a nuclear fuel rod 40 and preferably positioned axially near the top of the fuel rod 40 in the upper plenum region, as shown in FIG. 5 .
- the electronic enclosure 10 also includes a neutron barrier 20 surrounding the electronic components.
- Neutron barrier 20 includes a neutron reflecting material and a neutron absorbing material.
- the neutron reflecting material 22 When a neutron interacts with the electronic enclosure 10 , the neutron reflecting material 22 will act as the first layer of the neutron barrier 20 to shield the electronic components from neutrons.
- Beryllium Oxide (BeO) for example, is suitable as the neutron reflecting material because it has very low thermal and fast nuclear absorption cross sections but a relatively high scattering cross section. When neutrons interact with BeO the majority will scatter elastically away from the sensitive electronics. Many neutrons will be reflected back into the moderator.
- a moderator as used herein, means the material that surrounds the fuel rod and thermalizes, or slows down, the neutrons. In a pressurized water reactor, for example, the moderator is water.
- the neutron absorbing material 24 provides the second layer of the neutron barrier 20 to shield the electronic components from neutrons.
- Gadolinium (Gd) containing materials are examples of suitable neutron absorbing materials. Gadolinium in the form of gadolinium oxide or gadolinium isotopes Gd-155 and Gd-157 have the highest neutron capture rate of any stable isotope with thermal absorption cross-sections of 61,000 and 254,000 barns respectively. These materials will be very effective at absorbing thermal neutrons and protecting the sensitive electronics.
- BeO and Gd 2 O 3 are not required for the neutron reflecting and neutron absorbing materials and are listed as examples only. There are other commercially available ceramics with highly reflective and absorptive properties.
- neutron reflecting materials useful in the neutron barrier 20 include beryllium, beryllium oxides, beryllium nitrides or beryllium carbides.
- neutron absorbing materials include gadolinium metals, gadolinium oxides, gadolinium isotopes, ceramic compounds of gadolinium, cadmium metals, cadmium oxides, born metals, boron oxides, hafnium metals, hafnium oxides, etc.
- the materials are most preferably made of the ceramic forms of the base materials to ensure high temperature operation and also to act as an electrical insulation barrier for the conductive electronics.
- the use of a support structure 26 in certain embodiments as the primary structural support or in certain embodiments as an additional structural support, provides structure for enclosure 10 in the event degradation weakens the neutron barrier 20 .
- the structural support 26 may be made of a neutron transparent material that is neither a neutron reflecting nor a neutron absorbing material.
- the neutron transparent material may be a ceramic material, and may preferably be made of alumina (Al 2 O 3 ).
- the enclosure body 14 may be formed from a structural support 26 and one or more neutron barrier layers.
- the neutron barrier 20 may be formed from a solid neutron reflective layer 22 that surrounds a solid neutron absorbing layer 24 . Both surround cavity 18 .
- neutron reflective layer 22 may provide the structural support and an additional or separate support structure 26 may be eliminated.
- FIG. 2 illustrates a configuration for the neutron barrier 20 wherein the neutron reflecting layer 22 and the neutron absorbing layer 24 act both as the structural support and the neutron shield for the electronic enclosure 10 .
- the solid neutron reflective layer 22 may alone function as the structural support to give enclosure body 14 its solid structure.
- enclosure body 14 comprises the solid neutron reflective layer 22 surrounding the solid neutron absorbing layer 24 .
- the neutron reflecting layer may be made of beryllium or a beryllium containing compound, such as beryllium oxide (BeO).
- the neutron absorbing layer may be made of gadolinium or a gadolinium containing compound, such as gadolinium oxide (Gd 2 O 3 ).
- FIG. 3 schematically illustrates an alternative embodiment of enclosure 10 wherein the outermost layer is a structural support 26 , made of a neutron transparent material, such as a ceramic material.
- the ceramic material used for support structure 26 may be alumina. The use of alumina is well understood in nuclear applications and will provide either primary structural support or additional structural support for enclosure 10 .
- the structural support 26 surrounds a solid neutron reflective layer 22 which in turn surrounds a solid neutron absorbing layer 24 , which surrounds cavity 18 .
- the neutron absorbing material 24 may be in the form of a powder which fills the spaces in cavity 18 that remain after the electronics components are inserted into the cavity 18 .
- a neutron absorbing material 24 in powdered form is packed into cavity 18 and any other cavities 32 or passages 28 and 36 to fill any voids not filled by the electronics.
- FIG. 4 schematically illustrates a configuration of enclosure 10 having, for example, an alumina (Al 2 O 3 ) ceramic structural support 26 surrounding a solid neutron reflecting layer 22 which surrounds a cavity 18 filled with a neutron absorbing material 24 in powder form.
- the powdered neutron absorbing material 24 may be in the form of pressed powdered layer lining the interior of cavity 18 surrounding the electronic components.
- the reflecting and absorbing layers may both be in powdered form surrounded by a non-reflecting, non-absorbing structural support 26 .
- both BeO and Gd 2 O 3 are available in powder form.
- the powders may be in the form of a homogenous mixture or may be in the form of pressed powdered layers, with alternating layers of at least one layer of each of the neutron reflecting and absorbing materials 22 , 24 .
- FIG. 5 illustrates one configuration of enclosure 10 wherein neutron barrier 20 is in powdered form packed around the sensitive electronics (not shown).
- a solid reflecting layer 22 comprising a first part of neutron barrier 20 may act as the support structure 26 and surround cavity 18 .
- the neutron absorbing material comprising a second part of the neutron barrier 20 may be in the form of a powder packed around the electronic components and filling spaces in cavity 18 not occupied by the electronic components, such as the wire passages 36 and 28 .
- the powdered neutron absorbing material 24 may be in the form of pressed powdered layer lining the interior of cavity 18 surrounding the electronic components.
- FIG. 5 there may be at least two neutron absorbing layers in different positions within enclosure 10 .
- An initial or forward neutron absorbing layer 38 is shown.
- the forward neutron absorbing layer 38 may provide an initial shield against neutrons coming from the nuclear fuel rod 40 .
- the forward neutron absorbing layer 38 may be placed below the electronics cavity 18 between the center of the reactor core and the sensitive electronics. It is understood that neutrons in the plenum region of a nuclear fuel rod 40 will come from all directions but will have an upward bias, in the direction shown by arrow 46 .
- enclosure 10 shields the electronics from neutrons that come from the center of the core that have this upward bias.
- the placement of the forward neutron absorbing layer 38 in the path of the neutron flow will cast a “neutron shadow” 44 over the electronics as illustrated in FIG. 5 , absorbing neutrons that might otherwise have been directed toward the area of the shadow 44 .
- the forward neutron absorbing layer 38 may be a block of a solid material, such as a gadolinium containing material or any of the neutron absorbing materials discussed above. As stated above, gadolinium oxide is only one of several materials that may be used in the neutron barrier 20 . Gd metal (or another material with a high neutron cross section) may be used as the forward neutron absorbing layer 38 .
- a benefit from forward neutron absorbing layer 38 is that it can be made thicker than the absorbing layer forming part of the enclosure 10 or packed in the cavity 18 .
- the thicker layer 38 will therefore be able to absorb more neutrons.
- the neutron barrier 20 can be made from electrically conductive metal, such as cadmium, boron, hafnium, and gadolinium, without shorting any of the electronics because it can be separated from the components.
Abstract
Description
Claims (11)
Priority Applications (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US16/210,407 US11424046B2 (en) | 2018-12-05 | 2018-12-05 | Electronic enclosure with neutron shield for nuclear in-core applications |
PCT/US2019/059959 WO2020117415A1 (en) | 2018-12-05 | 2019-11-06 | Electronic enclosure with neutron shield for nuclear in-core applications |
EP19893862.3A EP3891763A4 (en) | 2018-12-05 | 2019-11-06 | Electronic enclosure with neutron shield for nuclear in-core applications |
JP2021532123A JP2022511530A (en) | 2018-12-05 | 2019-11-06 | Electronic component housing with neutron shield applied in the furnace |
KR1020217020437A KR20210088728A (en) | 2018-12-05 | 2019-11-06 | Electronics enclosure with neutron shielding for in-nuclear application |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US16/210,407 US11424046B2 (en) | 2018-12-05 | 2018-12-05 | Electronic enclosure with neutron shield for nuclear in-core applications |
Publications (2)
Publication Number | Publication Date |
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US20200185116A1 US20200185116A1 (en) | 2020-06-11 |
US11424046B2 true US11424046B2 (en) | 2022-08-23 |
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Application Number | Title | Priority Date | Filing Date |
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US16/210,407 Active 2039-10-23 US11424046B2 (en) | 2018-12-05 | 2018-12-05 | Electronic enclosure with neutron shield for nuclear in-core applications |
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US (1) | US11424046B2 (en) |
EP (1) | EP3891763A4 (en) |
JP (1) | JP2022511530A (en) |
KR (1) | KR20210088728A (en) |
WO (1) | WO2020117415A1 (en) |
Families Citing this family (4)
Publication number | Priority date | Publication date | Assignee | Title |
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US11424046B2 (en) | 2018-12-05 | 2022-08-23 | Westinghouse Electric Company Llc | Electronic enclosure with neutron shield for nuclear in-core applications |
WO2021202882A1 (en) | 2020-04-01 | 2021-10-07 | Holtec International | Storage system for radioactive nuclear waste with pressure surge protection |
CN113481503A (en) * | 2020-11-06 | 2021-10-08 | 江苏清联光电技术研究院有限公司 | Preparation method of boron particle reinforced metal matrix composite material, composite material and application thereof |
JP2023551521A (en) | 2021-07-06 | 2023-12-08 | エルジー エナジー ソリューション リミテッド | Battery cells and battery modules containing them |
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